Science and Technology of Nuclear Installations

Papers
(The median citation count of Science and Technology of Nuclear Installations is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-03-01 to 2025-03-01.)
ArticleCitations
Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation23
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model19
Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 113
Optimization of the n/γ Pulse Shape Discrimination Performance of Plastic Scintillator Coupled With SiPM Arrays11
Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code9
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions9
A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants8
Nuclear Power Sustainability Path for China from the Perspective of Operations8
A Hybrid Method to Predict the Remaining Useful Life of Scroll Wheel of Control Rod Drive Mechanism6
Count Loss Evaluation for Accuracy Enhancement of a FPGA‐Based Gamma Spectroscopy6
Inelastic Form Factor Calculations for 46,48,50Ti Isotopes Using Tassie Model6
Deep Learning–Based Fault Identification Testing Experiment for Bellows Valves6
Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube5
Study on Probabilistic Safety Goals for Multimodule High-Temperature Gas-Cooled Reactor Based on Chinese Societal Risks5
Migration Simulation of Radioactive Soil Particles in the Atmospheric Environment Using CFD-DEM Coupled with Empirical Formulas5
Prediction of the Loss of Feed Water Fault Signatures Using Machine Learning Techniques5
A New Experimental Method for the Nonlinear Modal Parameter Identification of a Pressurized Water Reactor Fuel Assembly4
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material4
Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion4
Application of EDG AOT Extension Based on the Risk-Informed Method in NPPs4
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem4
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials4
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant4
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process4
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger3
Single-Vehicle Transportation Security System of Radioactive Materials Based on Group Relationship to Prevent Loss and Theft3
A Study on Radiological Evaluation According to Exposure Conditions in Mobile Radiochemistry Analysis Facilities Using Worker’s Dose Evaluation Code3
Development and Experimental Validation for Quantifying the Moisture Carryover in a Moisture Separator Using an Air/Water Test Facility3
Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt3
Study of the Design and Assembly of a High Harmonic Fast Wave Antenna for an LAPD3
COMSOL Simulation for Design of Induction Heating System in VULCAN Facility3
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall3
Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method3
Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel3
Prediction of Crack Propagation Directions in Dissimilar Metal‐Welded Joints Using Phase‐Field Models and Discussion of Its Mechanisms3
Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean3
Source Reconstruction of Atmospheric Releases by Bayesian Inference and the Backward Atmospheric Dispersion Model: An Application to ETEX-I Data3
Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models3
Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance3
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION3
Radiation Tolerant 3D Laser Scanner for Structural Inspections in Nuclear Reactor Vessels and Fuel Storage Pools2
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants2
Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant2
Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland2
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints2
Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART2
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA2
The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel2
Research and Implementation of SVDU Simulator Based on Emulation Technology2
Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident2
Feasibility Study on the Initial Kartini Reactor Core Using Plate Type Fuel Elements2
The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code2
Cracking Driving Force at the Tip of SCC under Heterogeneous Material Mechanics Model of Safe-End Dissimilar Metal-Welded Joints in PWR2
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events2
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework2
Integrated Security System (ISS) Design and Evaluation for Commercial Nuclear Power Plant2
Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library2
Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite2
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump2
Studying Disturbance Wave Velocity and Wall Shear Stress of Vertical Upward Annular Flow in Narrow Rectangular Channel2
Effect of Photomultiplier Tube Voltage on the Performance of Sealed NaI (Tl) Scintillator Detectors1
Determination of the Activity Inventory in the Structural Components of the Dalat Nuclear Research Reactor for Its Decommissioning Planning1
Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel1
Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR10001
Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management1
Experimental and Numerical Studies of AP1000 Shield Building considering Fluid-Structure Interaction1
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method1
Effect of Thickness and Compaction Degree of Overburden Soil on Radon Reduction for Uranium Tailings Reservoir1
Cenosphere‐Based 177Lu‐Aluminosilicate Microspheres as a Theranostic β‐Emitter for Selective Internal Radiation Therapy of Hepatic Tumors1
Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site1
Design of Control System of Once-Through Steam Generator Based on Proximal Policy Optimization Algorithm1
Machine Learning-Based Approach for Hydrogen Economic Evaluation of Small Modular Reactors1
Proposal and Validation of a Diagnosis Method of Fuel Failures in Pressurized Water Reactor Nuclear Power Plants1
Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay1
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response1
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway1
Interaction of Mechanical Heterogeneity and Residual Stress on Mechanical Field at Crack Tips in DMWJs1
Experimental Study of Onset of Nucleate Boiling in Vertical Rectangular Channels with Different Flow Path Heights1
Uranium Decontamination from Waste Soils by Chlorination with ZrCl4 in LiCl-KCl Eutectic Salt1
Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System1
Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor1
Radiation Resistance of a Structural Material Based on Modified Titanium Hydride1
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library1
1
Overview on Radiation Damage Effects and Protection Techniques in Microelectronic Devices1
Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode1
Numerical Study of Unsteady Pressure Fluctuation at Impeller Outlet of a Centrifugal Pump1
Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B‐VIII.0 and JENDL‐5 Libraries for 10 MWth Micro Heat Pipe‐Cooled Reactor1
Simulation of Ionizing/Displacement Synergistic Effects on NPN Bipolar Transistors Irradiated by Mixed Neutrons and Gamma Rays1
Analysis of the Effect of Applied Load on Crevice Corrosion Behavior1
The Implementation of Diverse Actuation System in ACPR1000 Nuclear Power Plants1
High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment1
Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors1
Innovative Design of Compact Heavy-Load Independent Transfer Device for Nuclear Engineering System1
Inerting Strategy for a Demonstration-Scale Hot Cell Facility Based on Experiences from Pilot-Scale Argon Cell Facility Operation and CFD Analysis1
Shielding Design and Dose Evaluation for HTR-PM Fuel Transport Pipelines by QAD-CGA Program1
Simulation of Hydrogen‐Induced Cracking Behavior of Austenitic Stainless Steel 316L With Phase‐Field Method1
An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes1
A Novel Transformer‐Based Anomaly Detection Model for the Reactor Coolant Pump in Nuclear Power Plants1
Investigation of the Water Draining Process Pushed by Gas for U-Type and Z-Type Manifolds1
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